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Category:Letter type:TMI
MONTHYEARTMI-24-007, Re 2023 Commitment Revision Summary Report2024-04-29029 April 2024 Re 2023 Commitment Revision Summary Report TMI-23-018, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation TMI-23-013, Radiological Emergency Plan Document Revision2023-05-30030 May 2023 Radiological Emergency Plan Document Revision TMI-23-009, Submittal of Changes to Technical Specifications Bases2023-04-13013 April 2023 Submittal of Changes to Technical Specifications Bases TMI-23-004, Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 12023-03-21021 March 2023 Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 1 TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan TMI-23-002, Radiological Emergency Plan Document Revision2023-02-23023 February 2023 Radiological Emergency Plan Document Revision TMI-22-028, Radiological Emergency Plan Document Revisions2022-09-27027 September 2022 Radiological Emergency Plan Document Revisions TMI-22-016, 2021 Annual Radiological Effluent Release Report2022-04-25025 April 2022 2021 Annual Radiological Effluent Release Report TMI-22-017, 2021 Annual Radiological Environmental Operating Report2022-04-25025 April 2022 2021 Annual Radiological Environmental Operating Report TMI-22-018, 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20212022-04-19019 April 2022 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2021 TMI-22-015, Submittal of Changes to Technical Specifications Bases2022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases TMI-22-009, Registration of Use of Casks to Store Spent Fuel2022-03-0909 March 2022 Registration of Use of Casks to Store Spent Fuel TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 TMI-22-004, Registration of Use of Casks to Store Spent Fuel2022-02-0606 February 2022 Registration of Use of Casks to Store Spent Fuel TMI-21-027, Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-08-30030 August 2021 Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme TMI-21-024, 90-Day Notification Prior to First Storage of Spent Fuel2021-06-15015 June 2021 90-Day Notification Prior to First Storage of Spent Fuel TMI-21-025, Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities2021-06-15015 June 2021 Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities TMI-21-026, Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation2021-06-15015 June 2021 Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation TMI-21-018, License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan2021-04-29029 April 2021 License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan TMI-21-019, Submittal of 2020 Annual Radiological Environmental Operating Report2021-04-27027 April 2021 Submittal of 2020 Annual Radiological Environmental Operating Report TMI-21-017, Submittal of 2020 Annual Radiological Effluent Release Report2021-04-27027 April 2021 Submittal of 2020 Annual Radiological Effluent Release Report TMI-21-021, (TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20202021-04-27027 April 2021 (TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2020 TMI-21-009, License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-03-0404 March 2021 License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme TMI-20-027, Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License2020-10-0909 October 2020 Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License TMI-20-026, Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation2020-09-15015 September 2020 Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation TMI-20-025, Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report2020-07-16016 July 2020 Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report TMI-20-021, Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative2020-07-0808 July 2020 Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative TMI-20-015, 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report2020-04-30030 April 2020 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report TMI-20-016, 2019 Annual Radiological Environmental Operating Report2020-04-30030 April 2020 2019 Annual Radiological Environmental Operating Report TMI-20-017, 2019 Annual Radiological Effluent Release Report2020-04-30030 April 2020 2019 Annual Radiological Effluent Release Report TMI-20-012, Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases2020-04-13013 April 2020 Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases TMI-20-002, Annual Notification of Property Insurance Coverage2020-03-25025 March 2020 Annual Notification of Property Insurance Coverage TMI-20-006, Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7)2020-03-0202 March 2020 Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7) TMI-19-112, Application for Order Approving License Transfer and Conforming License Amendments2019-11-12012 November 2019 Application for Order Approving License Transfer and Conforming License Amendments TMI-19-097, License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-10-31031 October 2019 License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements TMI-18-100, Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition2018-10-29029 October 2018 Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition TMI-18-088, Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report2018-08-21021 August 2018 Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report TMI-18-024, Biennial 10 CFR 50.59 and Pdms SAR Report2018-04-24024 April 2018 Biennial 10 CFR 50.59 and Pdms SAR Report TMI-18-044, Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 292018-03-29029 March 2018 Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 29 TMI-18-004, Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 22018-03-16016 March 2018 Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 2 TMI-18-017, Annual Report2018-02-12012 February 2018 Annual Report TMI-17-093, Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 252017-08-18018 August 2017 Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 25 TMI-17-060, Request for Approval of Certified Fuel Handler Training Program2017-07-10010 July 2017 Request for Approval of Certified Fuel Handler Training Program TMI-17-051, Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 20132017-05-16016 May 2017 Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 2013 TMI-17-035, Submittal of Changes to Technical Specifications Bases2017-04-13013 April 2017 Submittal of Changes to Technical Specifications Bases TMI-17-034, Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04)2017-03-31031 March 2017 Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04) TMI-17-006, Decommissioning Funding Status Report2017-03-24024 March 2017 Decommissioning Funding Status Report TMI-16-097, Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 172016-10-20020 October 2016 Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 17 TMI-16-082, Notice of Transfer of Transmission Asset2016-09-15015 September 2016 Notice of Transfer of Transmission Asset 2024-04-29
[Table view] Category:Report
MONTHYEARML23073A3982023-03-31031 March 2023 TMI-2 ISFSI Biennial Update Report for 2023 TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan ML22335A4632022-12-0101 December 2022 Chronology of Significant Events in Operator Licensing Since the Three Mile Island Accident (1979) ML22101A0792022-03-23023 March 2022 TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 ML22105A0932021-12-16016 December 2021 Attachment 3 - RSCS Technical Support Document (Tsd) No. 21-078 Rev 00 TMI-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 Rem EPA PAG ML21236A2882021-08-10010 August 2021 TMI-2 Pdms SAR Update 14 & QA Plan (Rev 18 & 19) Biennial Submittal 08-10-21 ML21133A2642021-05-0505 May 2021 Supplemental Information to License Amendment Request Decommissioning Technical Specifications ML21084A2292021-03-17017 March 2021 Notification of Amended Post-Shutdown Decommissioning Activities Report Accordance with 10 CFR 50.82(a)(7), Revision 4 ML21085A6922021-03-15015 March 2021 Plan for Management of Debris Material ML21056A0052021-02-25025 February 2021 2020 Aircraft Movement Data Annual Report ML21133A2652021-02-0101 February 2021 Calculation TMI2-EN-RPT-0002, Revision 0, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library ML18107A2152018-04-10010 April 2018 Biennial 10 CFR 50.59 and Commitment Revision Reports for 2016 and 2017 ML17289A0532017-10-15015 October 2017 Case Study Overview ML17165A4092017-06-14014 June 2017 T1R22 Refuel Outage MRP-227-A Reactor Internals Scope Deferral Review RS-16-104, Mitigating Strategies Flood Hazard Assessment Submittal2016-06-29029 June 2016 Mitigating Strategies Flood Hazard Assessment Submittal RS-16-087, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-06-29029 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML15306A5032015-12-17017 December 2015 Closure Evaluation for Report Pursuant to 10 CFR 50.46 Requirements Related to Thermal Conductivity Degradation ML15223A2152015-08-14014 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights TMI-15-076, Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue2015-06-22022 June 2015 Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue ML15043A1442015-02-13013 February 2015 Review of Steam Generator Tube Inspection Report for Fall 2013 Outage ML14297A4112014-12-19019 December 2014 Letter and Non-Proprietary Safety Evaluation of Reactor Vessel Internals Inspection Plan RS-14-301, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-17017 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14163A0242014-06-10010 June 2014 Response to Request for Additional Information - Review of the Cycle 20 Core Operating Limits Report ML14189A2852014-04-30030 April 2014 Topical Report 213, 40th Year Reactor Building Tendon Surveillance (Period 10), (Rev 0) ML14189A2862014-04-17017 April 2014 Final Report for the 40th Year (10th Period) Tendon Surveillance at Three Mile Island, Unit 1 TMI-14-053, Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 20132014-04-16016 April 2014 Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 2013 ML13225A5522013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6712013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Three Mile Island, Unit 1, TAC MF0803 ML14189A2872013-11-12012 November 2013 TMI 40TH Year Tendon Surveillance, Tendon No. 1-146-34, Tendon End Buddress 4 TMI-14-061, 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs)2013-09-0303 September 2013 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs) TMI-13-107, Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 20132013-08-31031 August 2013 Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 2013 ML13232A2172013-07-31031 July 2013 Attachment 2 - Areva Document No. ANP-3102, Revision 3,Three-Mile Island Unit 1 Appendix G Pressure-Temperature Limits at 50.2 EFPY with Mur, Revision 3, Dated July 2013 TMI-13-041, Post-Shutdown Decommissioning Activities Report Submittal2013-06-28028 June 2013 Post-Shutdown Decommissioning Activities Report Submittal TMI-12-148, Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-022013-05-16016 May 2013 Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02 IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12362A0422012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page C-1 Through Page C-161 ML12362A0432012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page C-162 Through Page C-284 2023-03-31
[Table view] Category:Miscellaneous
MONTHYEARTMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan ML22335A4632022-12-0101 December 2022 Chronology of Significant Events in Operator Licensing Since the Three Mile Island Accident (1979) TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 ML21085A6922021-03-15015 March 2021 Plan for Management of Debris Material ML21056A0052021-02-25025 February 2021 2020 Aircraft Movement Data Annual Report ML18107A2152018-04-10010 April 2018 Biennial 10 CFR 50.59 and Commitment Revision Reports for 2016 and 2017 ML17289A0532017-10-15015 October 2017 Case Study Overview ML17165A4092017-06-14014 June 2017 T1R22 Refuel Outage MRP-227-A Reactor Internals Scope Deferral Review RS-16-104, Mitigating Strategies Flood Hazard Assessment Submittal2016-06-29029 June 2016 Mitigating Strategies Flood Hazard Assessment Submittal ML15306A5032015-12-17017 December 2015 Closure Evaluation for Report Pursuant to 10 CFR 50.46 Requirements Related to Thermal Conductivity Degradation ML15223A2152015-08-14014 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights TMI-15-076, Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue2015-06-22022 June 2015 Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue ML15043A1442015-02-13013 February 2015 Review of Steam Generator Tube Inspection Report for Fall 2013 Outage ML14297A4112014-12-19019 December 2014 Letter and Non-Proprietary Safety Evaluation of Reactor Vessel Internals Inspection Plan RS-14-301, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-17017 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. ML14163A0242014-06-10010 June 2014 Response to Request for Additional Information - Review of the Cycle 20 Core Operating Limits Report TMI-14-053, Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 20132014-04-16016 April 2014 Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 2013 TMI-13-041, Post-Shutdown Decommissioning Activities Report Submittal2013-06-28028 June 2013 Post-Shutdown Decommissioning Activities Report Submittal TMI-12-148, Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-022013-05-16016 May 2013 Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02 IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12178A2152012-08-0202 August 2012 Closeout of Bulletin 2011-01 Migrating Strategies. E910-11-007, Gpu Nuclear, TMI 2 Defueling Completion Report2011-04-11011 April 2011 Gpu Nuclear, TMI 2 Defueling Completion Report ML1023505272010-08-18018 August 2010 Buried Piping - Inspecting Something You Can'T See TMI-10-029, Biennial 10 CFR 50.59 and Commitment Revision Reports for 2008 and 20092010-04-15015 April 2010 Biennial 10 CFR 50.59 and Commitment Revision Reports for 2008 and 2009 ML0828804502008-10-14014 October 2008 2008 PA Fishing Summary - Summary of Fishing Regulations and Laws ML0824101022008-06-12012 June 2008 Report of Tornadoes in Dauphin County, PA Between 01/01/1950 and 05/31/2008, NCDC ML0815801742008-05-30030 May 2008 License Renewal Environmental Impact Statement ML0824100852008-05-0101 May 2008 Comprehensive Plan for the Water Resources of the Susquehanna River Basin, Draft ML0819807102008-04-0303 April 2008 C2-WHC 2005 - Site Assessment and Wildlife Management Opportunities Report for Exelon Corporation'S Three Mile Island Generating Station. October ML0830502322008-03-11011 March 2008 Pjm 2007 State of the Market Report ML0816106632008-02-14014 February 2008 Biennial 10 CFR 50.59 and Pdms SAR Report for Years 2006 & 2007 ML0612100392006-04-19019 April 2006 Biennial 10 CFR 50.59 and Commitment Revision Report for 2004 and 2005 ML0505301682005-02-17017 February 2005 Background Discussion Material for February 24-25, 2005 NRC Meeting Relating to Replacement for BAW-2374, Revision 1, Evaluation of OTSG Thermal Loads During Hot Leg Loca. ML0309006042003-03-19019 March 2003 Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC ML0303506252003-01-23023 January 2003 Request for NRC Written Consent to Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC ML0231803602002-11-0404 November 2002 (TMI-1) Emergency Notification System Warning Sirens ML0224802942002-08-28028 August 2002 Fitness-for-Duty Program Performance Data (FFD) for the Period - January 2002 Through June 2002 ML0224901882002-08-27027 August 2002 Fire Hazards Analysis Report (Fhar), Rev 20, Appendix R Evaluation Report, Cables & Components in Fire Area/Zone, Volume II, Attachment 3-7 ML0224901792002-08-27027 August 2002 Fire Hazards Analysis Report (Fhar), Rev 20, Appendix R Evaluation Report, Component Availability for a Fire in Fire Area/Zone, Volume II, Attachments 3-51 - 3-61 2023-03-21
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Exelon Generation, Three Mile Island Unit 1 Telephone 717-948-8000 Route 441 South, P.O. Box 480 Middletown, PA 17057 April 16, 2014 TMI-14-053 U. S. Nuclear Regulatory Commission, Region I Attn: Document Control Desk Washington, D.C. 20555 THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1)
RENEWED FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
SUBJECT:
BIENNIAL 10 CFR 50.59 AND COMMITMENT REVISION REPORTS FOR 2012 AND 2013 Enclosed are the 2012 - 2013 Biennial 10 CFR 50.59 and Commitment Revision Reports as required by 10 CFR 50.59(d)(2) and SECY-00-0045 (NEI 99-04).
There are no regulatory commitments contained in this transmittal.
If you have any questions or require additional information, please contact Mike Fitzwater, of Regulatory Assurance, at 717-948-8228.
Sincerely, Kk-NA. c- rý Mark Newcomer Plant Manager, TMI-1 Exelon Generation Co., LLC MN/mdf Enclosure cc: USNRC Regional Administrator, Region I USNRC Project Manager, TMI USNRC Senior Resident Inspector, TMI
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2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports THREE MILE ISLAND UNIT 1 DOCKET NO. 50-289 BIENNIAL 10 CFR 50.59 AND COMMITMENT REVISION REPORTS TABLE OF CONTENTS 10 CFR 50.59 Report 2 Modifications 3 Procedure Changes 6 Commitment Revision Report 7 1
2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports EXELON CORPORATION THREE MILE ISLAND UNIT 1 DOCKET NO. 50-289 BIENNIAL 10 CFR 50.59 REPORT JANUARY 1, 2012 THROUGH DECEMBER 31, 2013 10 CFR 50.59 EVALUATION SUMMARIES 2
2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports Modifications
Title:
ECR 11-00487 - 50.59 Evaluation for River Stage Discharge Analysis Year Implemented: 2012 Evaluation Number: Engineering Change Request No. TM 11-00487 ECR TM-1 1-00487 Brief
Description:
"River Stage Discharge and Discharge Frequency Analysis" (C-1 101-122-E410-003 RO) has been completed. The affected design and licensing documents were updated based on the results of that analysis. The revised conclusions of the stage discharge analysis are not based on a change in design at TMI. The change is a product of updated gage data from Marietta USGS station, recent topographical and bathymetric surveys, the post Agnes configuration of the Shocks Mill Railway bridge, and calibration of the model to 1972 flood (1,002,000 CFS) versus 1936 flood (740,000 CFS).
The new analysis predicted a peak water surface elevation during a probable maximum flood is higher and the predicted frequency of occurrence of a probable maximum flood is lower than previously predicted. The net affect of complete results of the new analysis is no adverse impact on nuclear safety. TMI-1 flood protection was previously improved. The probability of an event where the river water level exceeds the flood protection is lower than understood during original licensing.
Summary of Conclusion for the Activity's 50.59 Review:
An evaluation of affects of the higher PMF water surface elevation was completed. The key conclusions included that there is no increase in the likelihood of malfunction of the dike or flood barrier system and the frequency of occurrence of a PMF has not increased.
Therefore, these changes do not require prior NRC approval.
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2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports
Title:
ECR 12-00129 - 50.59 Evaluation for TMI-1 50.2 EFPY P-T Limits Year Implemented: 2012 Evaluation Number: Engineering Change Request No. TM 12-00129 ECR TM-12-00129 Brief
Description:
The proposed activity will update Reactor Coolant System (RCS) Pressure-Temperature (P-T) limits for continued plant operation through 50.2 Effective Full Power Years (EFPY). The changes to the existing P-T limits implemented by this modification include: Replacement of the heat up and cooldown curves found in Technical Specifications (TS) Figures 3.1-1 and 3.1-2; the adjustment of the Power Operated Relief Valve (PORV) Low Temperature Overpressure Protection (LTOP) setpoint from 552 psig to 592 psig; establishment of new heat up and cooldown LTOP enable temperature from 329 degF to 313 degF; and the revision of the existing P-T limits related TS 3.1.2.4 commitment for operation beyond 50.2 EFPY.
A License Amendment Request (LAR) was prepared for this modification to request NRC approval for the use of the BAW-2308 methodology for the determination of the initial Reference Temperature Nil Ductility Transition (RTNDT) for the Linde 80 Reactor Vessel (RV) beltline weld materials. The use of the BAW-2308 methodology is an exception to the requirements of 1 OCFR50, Appendix G and 10CFR50.61 for the determination of initial RTNDT, used for the determination of the Adjusted Reference Temperature (ART) and Reference Temperature for Pressurized Thermal Shock (RTPTS) for RV beltline materials.
The LAR will also request NRC approval for the changes to various technical specifications related to the RCS P-T limits. Implementation of the design analyses and procedure changes will be addressed in the 50.59 screening.
Multiple procedures will also be updated to implement the revised P-T limits and the PORV setpoint change for operation through 50.2 EFPY.
The reason for the activity is due to the existing RCS P-T limits as provided in the TS are applicable for plant operation through 29 EFPY. TS 3.1.2.4 states, "Prior to exceeding 29 effective full power years of operation, Figures 3.1-1 and 3.1-2 shall be updated for the next service period in accordance with 10CFR50, Appendix G." Plant operation is approaching the 29 EFPY limit, therefore it is necessary to replace the existing P-T limits to ensure plant operation beyond 29 EFPY.
The effect of the activity is that this modification will implement updated P-T limits intended for plant operation through 50.2 EFPY to replace the existing P-T limits for plant operation through 29 EFPY. Specifically, this modification will provide:
e Revised PORV LTOP setpoint (TS 3.1.12.2a.2) 4
2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports
" Revised P-T limits (curves) for RCS heat up / cooldown and ISLH operations (TS Figures 3.1-1 and 3.1-2)
- Revised heat up and cooldown LTOP enable temperatures (TS 3.1.12.1, 3.1.12.2.a.1, 3.1.12.3, 3.1.12 Bases, and 4.5.2.1.c.1)
- Revise the commitment to update TS P-T limits to the next service period prior to exceeding 50.2 EFPY (TS 3.1.2.4)
Use of the updated P-T limits will ensure continued safe operation of the TMI-1 RCS through 50.2 EFPY. The intended actions within the procedures remain the same. There is no adverse impact on plant operations on how RCS heat up and cooldown is performed during planned and unplanned (emergency) situations.
This modification will require NRC acceptance of the TMI-1 license amendment request for the use of the BAW-2308 methodology to determine the initial RTNDT of the RV beltline Linde 80 weld material and to implement updated TS P-T limits.
Summary of Conclusion for the Activity's 50.59 Review:
The Screening review of this proposed activity determined that a 10CFR50.59 evaluation must be performed to determine the acceptability for the use of the BAW-2308 alternative methodology for the determination of the initial RTNDT of the RV beltline Linde 80 weld material. Further, the NRC must approve a LAR for the use of the BAW-2308 methodology, and to implement TS changes described above.
The 10CFR50.59 evaluation prepared for the use of the BAW-2308 methodology demonstrates that this methodology may be used with no adverse effects on the design basis of any equipment, either safety related or non-safety related. This modification includes updates to the UFSAR in accordance with 1 OCFR50.71 (e).
For all other portions of this modification, the modification may be implemented with no adverse effects on the design basis of any equipment, either safety related or non-safety related. Further, all impacts have been evaluated to ensure that there are no adverse effects on plant equipment operation and personnel activities involved with implementation of the new P-T limits, the new LTOP enable temperatures, and the new LTOP PORV setpoint.
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2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports Procedure Changes There were no 10 CFR 50.59 required procedure changes for this reporting period.
End of 10 CFR 50.59 Revision Report 6
2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports EXELON CORPORATION THREE MILE ISLAND UNIT 1 DOCKET NO. 50-289 BIENNIAL COMMITMENT REVISION REPORT JANUARY 1, 2012 THROUGH DECEMBER 31, 2013 7
2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports Letter Source: IEB 90-01: Loss of Fill Oil in Rosemount Transmitters Exelon Tracking No.: 1990T0027 / 1122355-96 Nature of Commitment: GPUN committed to the NRC in its response to IEB 90-01 to:
- 1. Plot at least quarterly the control room log readings for the 12 low static pressure/non-safety related actuation functions to assure correct transmitter operation.
- 2. Trend calibration data for those Rosemount Transmitters identified as being in standby service and do not yield useful operating point trend data.
Summary of Justification:
Commitment Change Evaluation Form 12-01 revised this commitment from "Continuing" to "Historical". During a review of licensing commitments, it was determined that CMT:
1990T0027 related to Rosemount transmitter loss of fill oil may be deleted since the action was completed in 1992. The commitment was to plot control room indications and to trend calibration data until the affected transmitters were replaced. Close out of Licensing Action Item 90-9157 on Jan 22, 1992 documents completion of the action. This commitment is no longer needed since the action to replace the affected transmitters is complete.
Letter Source: C311-93-3140 Exelon Tracking No.: 1993T0027 / 1122355-63 Nature of Commitment: This verbal agreement was reflected in the cover letter and the SER for Tech Spec Amendment No. 175. The cover letter stated "The approval of this amendment is conditioned on the understanding that "Load Test", as used in TS Section 4.6.2, "Station batteries,' is interpreted to mean a modified performance test as described in IEEE Standard 450." The reference standard agreed to was IEEE standard 450-93 (Revision of IEEE standard 450-1987), an unapproved draft with revision date of November 16, 1992. To expedite NRC issuance of the amendment in time to support the TSCR 206, "24 month cycle surveillance extensions" for those surveillance coming due, the commitment was not described in GPUN correspondence or the TS Bases, the modified performance test was incorporated into 1303-11.11, Rev. 21 (effective 8/6/93).
Summary of Justification:
Commitment Change Evaluation Form 12-03 revised this commitment. Commitment revision was made due to the unavailability of IEEE 450-1993 in TMI database. Commitment was revised to IEEE 450-1995 since this was the approved version of this standard.
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2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports Letter Source: C311-92-2003: Safety Evaluation for compliance with 10CFR50.62 ATWS TAC 59151 Exelon Tracking No.: 1992T0018 / 1122355-60 Nature of Commitment: GPUN committed to the NRC to maintain ATWS diversity in a programmatic manner different from the referenced in the NRC Safety Evaluation Report (SER) referenced. This commitment requires that the diversity stipulation be captured in the UFSAR as well as in the Engineering Data Bases found in the computer based systems used to control repairs/replacements (GMS-2 Programs Resident on the IMSP Platform within the GPUN mainframe computer system. This phrase was replaced with the generic computer based system per CCT #07-020)
Summary of Justification:
Commitment Change Evaluation Form 12-05 revised this commitment. During a review of licensing commitments, it was determined that this commitment has been completed by an update to the UFSAR and by the ATWS field in PIMS. The ATWS diversity requirements are captured in UFSAR section 7.1.5. There is an ATWS field in the PIMS codes and classifications screens for all components.
Letter Source: 5211-82-2301: GL 81-14: EFW Seismic Qualification Exelon Tracking No.: 1982T0008 / 1122072-46 Nature of Commitment: GPUN committed to the NRC to isolate the emergency feedwater system by closing CO-V-111A/B and CO-V-14 A/B whenever a tank reached the technical specification limit following any EFW actuation at restart and during the interim period before the long term modifications are complete, following any recognizable seismic event.
Summary of Justification:
Commitment Change Evaluation Form 12-06 revised this commitment. During a review of this licensing commitment, it was determined that this commitment has been completed with added notation that the requirement to close CO-V-111A, CO-V-111 B, CO-V-14A and CO-V-1 4B has been retained after the modifications were completed per commitment 1983T0046.
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2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports Letter Source: GL 88-17: Expeditious Action 1 Exelon Tracking No.: 1998T0128 / 1122355-45 Nature of Commitment: Discuss the event that occurred at Diablo Canyon Nuclear Station and provide training on the event prior to entering a reduced inventory condition. This event involved a loss of residual heat removal while the reactor was shutdown and the core was in a reduced inventory condition.
Summary of Justification:
Commitment Change Evaluation Form 12-08 revised this commitment. There has been significant change at TMI - 1 and throughout the Nuclear Industry since 1988 regarding the control of plant systems during outages to ensure fuel protection. Shutdown safety is now addressed in the TMI 1 Long Range Training Plan and in OU-TM-1 03.
Letter Source: IEN 86-03: ECCS failure due to Recirculation Valve Exelon Tracking No.: 1986T0016 / 1122355-19 Nature of Commitment: GPUN committed to the NRC that the TMI-1 ECCS pump recirculation line design is acceptable.
Summary of Justification:
Commitment Change Evaluation Form 12-09 revised this commitment. Memo 3310 0118 documents the review of the results for the potential for a loss of minimum flow paths leading to ECCS pump damage during a LOCA. The report determined that TMI-1 does have a single recirculation line for the HPI pumps which is isolated automatically on ES actuation. The design was determined to be acceptable because: 1) The HPI pumps are high head and will provide enough flow at maximum RCS pressure to protect the pump for ES, 2) Loss of power does not isolate the recirculation line, and 3) the minimum flow requirements when HPI is manually throttled are addressed in procedures. Same issue addressed in IEN 85-94 Letter Source: Licensing Letter 6710-96-2097: GL 89-013: REVISED
RESPONSE
Exelon Tracking No.: 603573-10-34 / 1122072-01 Nature of Commitment: The Generic Letter states "Confirm that maintenance practices, operating and emergency procedures, and training that involves the service water system are adequate to ensure 10
2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports that safety-related equipment cooled by the service water system will function as intended and that operators of this equipment will perform effectively. This confirmation should include recent (within the past 2 years) reviews of practices, procedures, and training modules.
The response letter states "TMI-1 procedures are reviewed on a biennial basis which provides reasonable assurance that TMI-1 procedures are current and reflect plant configuration.
GPUN personnel review maintenance, operating, surveillance, emergency procedures, etc., dealing with open and closed cycle service water systems via this biennial review process.
In addition to the biennial review, other procedural changes are made as the result of vendor recommendations, plant modifications, License Amendments, etc. Furthermore, QA audits similar to those discussed in the response to Recommended Action IV, also serve to confirm the adequacy of procedures related to service water systems.
The TMI Training Department program for reviewing and maintaining lesson plans ensures that equipment and procedure changes are incorporate in lesson plans and that lesson plans are maintained current. Additional training is accomplished through on-the-job training, industrial experience, meetings, etc.
The recent Service Water System Self Assessment reviewed procedures and witnessed the use of procedures in response to a system transient at the TMI-1 simulator. This Self Assessment also reviewed training activities. The results found the procedures and training to be in good condition and operators knowledgeable of the procedures.
Thus GPU Nuclear has confidence that our current procedure and training program provide assurance that the safety-related equipment, and the Control Building chiller system, cooled by service water systems will perform their intended function and that operators of this equipment will perform effectively."
Summary of Justification:
Commitment Change Evaluation Form 12-10 revised this commitment. The Generic Letter asks for a confirmation of the adequacy of maintenance practices and operational procedures. This confirmation has been completed. The statements regarding continuing beyond the original scope of Action V of GL 89-13. These continuing procedural reviews and maintenance of training lesson plans are not a part of the GL 89-13 program but rather the QATR.
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2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports Letter Source: CAL NRR-07-029 (5928-07-20044)): SUPPLEMENTAL RESPONSE REGARDING INSPECTION AND MITIGATION OF ALLOY 600/82/182 PRESSURIZER BUTT WELDS Exelon Tracking No.: 1122355-80 / 603573-10 Nature of Commitment: The commitments associated with Passport 607832 are the result of required actions from 2007 for Alloy 600 degradation in pressurizer Dissimilar Metal Welds (DMW). Specifically TMI committed to:
- 1. Certain action levels for RCS leakage until the required six pressurizer welds (five locations) were inspected by UT or mitigated. The welds were inspected or mitigated during the 2007 refueling outage. The action levels have not been applicable since the 2007 refueling outage. Reference Passport assignment 607832.01 for the inspection/mitigation processes reported to the NRC.
- 2. Report inspection results to the NRC within 60 days of completion. Passport assignments 607832.01, .08, and .09 fulfilled the reporting commitments.
- 3. Re-examine the pressurizer spray nozzle dissimilar metal butt welds within four years if not mitigated prior to the Fall 2011 refueling outage. The pressurizer spray butt welds were examined and mitigated during the Fall 2011 refueling outage so this commitment is no longer applicable (reference passport assignment 607832.09 for reporting details.
Summary of Justification:
Commitment Change Evaluation Form 12-12 revised this commitment. All six pressurizer DMW butt welds associated with CAL NRR-07-029 are now mitigated and the commitment is no longer applicable. See Letter TMI-1 1-166.
Letter Source: LAR 96075.054 (GPUN Letter 1920-98-20242) and LAR 96075.08 (GPUN Letter 1920-99-20019)
Exelon Tracking No.: 1122072-28 & 30 Nature of Commitment: In response to NRC Generic Letter 96-05, Three Mile Island Unit 1 committed to implement the Joint Owners Group (JOG)
Program for Motor Operated Valve Periodic Verification in accordance with MPR-1807 (Interim) and MPR-2524-A Rev.1 12
2012-2013 Biennial 10 CFR 50.59 and Commitment Revision Reports (Final). Note: Not all GL96-05 MOV Program Valves are within the scope of the Final JOG Program.
Summary of Justification:
Commitment Change Evaluation Form 12-13 revised this commitment. The JOG Class D MOVs have been installed at Three Mile Island Unit 1 prior to 1989. Three Mile Island Unit 1 is following the JOG Program requirements to develop and justify an alternative method to address service related degradation. While this method is not reviewed and approved by the NRC, an engineering evaluation has been performed in order to justify its use.
Letter Source: 6710-96-2096 Attachment 1 GL 89-013: REVISED RESPONSE - SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPMENT Exelon Tracking No.: 1122072-01 Nature of Commitment: The Emergency Cooling Coils will be subject to a combination of visual inspections and trending. Visual inspection of the air side and monitoring of air and water flows will occur each outage.
Summary of Justification:
Commitment Change Evaluation Form 13-01 revised this commitment to monitor of air flows to every other outage. The purpose of PM009409 is to monitor the air flow through the RB containment coolers AH-E-1A/B/C. The flows are measured at low fan speed (emergency operating conditions) and high speed normal cooling operation. The PM monitors air flow only and is an assessment of the amount of flow obstructions (clogged fins) in the cooling coils. The historical basis for this PM was to ensure that the coolers do not become clogged with boron deposits as a result of RCS leakage which condenses out onto the coiling coils.
During power operations the air flow through AH-E-1A/B/C is monitored and trended per GA003857. Therefore an adverse trend in containment cooler air flow would be detected.
In addition, during refueling the cooling coils are visually inspected for deposits/ flow obstructions and cleaned as needed per PM208879. Consequently sufficient barriers and monitoring are currently in place to warrant changing the 1 R commitment of PM009409 to 2R.
Letter Source: NUREG-1928 Exelon Tracking No.: 603573-11 Nature of Commitment: UFSAR Appendix A section A.2.1.11 Inspection of Overhead Heavy Load and Light Load (related to refueling) Handling 13
2012-2013 Biennial10 CFR 50.59 and Commitment Revision Reports Systems (Attachment A of this review) states: Inspection frequency is annually for cranes and hoists that are accessible during plant operation and every 2 years for cranes and hoists that are only accessible during refueling outages.
NRC SER section 3.0.3.2.7 Inspection of Overhead Heavy Load and Light Load (related to refueling) Handling Systems states (pg 3-56) the commitment appropriately, so no clarification is necessary: Some more infrequently used cranes have an inspection frequency of either two years, or inspection prior to use.
The SER Appendix A, Commitment for License Renewal of TMI-1 requires no clarification, since there is no mention of the frequency of the inspections.
Summary of Justification:
Commitment Change Evaluation Form 13-02 revised this commitment. To make TMI's UFSAR match TMI's SER (NUREG-1928) from The NRC, which is consistent with the GALL (NUREG 1801) rev. 2 The GALL rev. 2 is the most recent and up to date guidance provided by the NRC.
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